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IAEA0925 SHARDA.

SHARDA, Thermal Reactor Isotope Irradiation Analysis

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1. NAME OR DESIGNATION OF PROGRAM:  SHARDA.
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2. COMPUTERS
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Program name Package id Status Status date
SHARDA IAEA0925/01 Tested 11-SEP-1987

Machines used:

Package ID Orig. computer Test computer
IAEA0925/01 NORSK DATA 500 CDC CYBER 740
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SHARDA is a program for assessing Sample Heating rate, activities produced and reactivity load caused while irradiating a small sample in a well thermalised research reactor like CIRUS. It estimates the sample cooling or lead shielding requirements to limit the gamma dose rates due to the irradiated sample within permissible level.
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4. METHOD OF SOLUTION

Various thermal neutron nuclear data, radiation data of activities produced by neutron capture (of consequence for gamma dose rate estimates) and the isotopic composition of all natural non-fissionable elements are compiled and built into the code. The data for gamma attenuation in lead are also incorporated.  Reactivity load per cm2 of a white absorber evaluated at a reference point in a reactor (CIRUS in the present varsion) and the relative thermal neutron flux levels at all permissible irradiation locations in the reactor are also built in. The parameters of interest for a given sample (defined by its chemical formula or mixture specification) and its irradiation specification are evaluated using this inbuilt data library and the analytical expressions for the parameters derived under certain approximations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Nil.
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6. TYPICAL RUNNING TIME:  A few seconds of CPU.
IAEA0925/01
NEA-DB ran the test case included in this package on a CDC CYBER 740 computer in 1.8 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

Since the code was basically developed for P.I.R. evaluations in the CIRUS research reactor, the  flux levels at various possible irradiation locations and the reactivity worth per cm2 of a white absorber area (at a reference point) built into the code pertain to CIRUS. To use the code for such analysis in any other well thermalised research reactor, these  parameters may be appropriately changed. The code can, however, be used as such for most of such analyses, except reactivity load, for  any other thermal research reactor by giving the absolute value of irradiating thermal neutron flux as input.
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8. RELATED AND AUXILIARY PROGRAMS:  Nil.
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9. STATUS
Package ID Status date Status
IAEA0925/01 11-SEP-1987 Tested at NEADB
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10. REFERENCES:
IAEA0925/01, included references:
- V.K. Shukla and Anil Bajpai:
  SHARDA - A Program for Sample Heat, Activity, Reactivity
  and Dose Analysis.
  B.A.R.C.-1259  (1985)
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11. MACHINE REQUIREMENTS:  About 100 Kbytes of core storage.
IAEA0925/01
The test case ran on a CDC CYBER 740 in 43621 (octal) words of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0925/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  SINTRAN- III Version J.
IAEA0925/01
NOS 2.5.1 (CDC CYBER 740) with FTN5.1+650 compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  Nil.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          V.K. Shukla and Anil Bajpai
          Reactor Services Division
          Bhabha Atomic Research Centre
          Bombay, India
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16. MATERIAL AVAILABLE
IAEA0925/01
File name File description Records
IAEA0925_01.001 information file 58
IAEA0925_01.002 SHARDA source program (FORTRAN-77) 1287
IAEA0925_01.003 sample problem input data 5
IAEA0925_01.004 sample problem printed output 426
IAEA0925_01.005 sample problem summary output (TAPE6) 70
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: capture, dose rates, gamma radiation, irradiation, isotopes, radiation heat, radioactivity, radioisotopes, reactivity, shielding, thermal reactors.